JPH0552475B2 - - Google Patents
Info
- Publication number
- JPH0552475B2 JPH0552475B2 JP58234186A JP23418683A JPH0552475B2 JP H0552475 B2 JPH0552475 B2 JP H0552475B2 JP 58234186 A JP58234186 A JP 58234186A JP 23418683 A JP23418683 A JP 23418683A JP H0552475 B2 JPH0552475 B2 JP H0552475B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- rods
- water
- fuel assembly
- rod
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
- 239000000446 fuel Substances 0.000 claims description 103
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 35
- 238000009835 boiling Methods 0.000 claims description 4
- 230000001147 anti-toxic effect Effects 0.000 claims 1
- 239000003440 toxic substance Substances 0.000 claims 1
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(iii) oxide Chemical compound [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 description 16
- 230000004907 flux Effects 0.000 description 7
- 239000008188 pellet Substances 0.000 description 7
- 230000000694 effects Effects 0.000 description 6
- 230000009257 reactivity Effects 0.000 description 5
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 238000002485 combustion reaction Methods 0.000 description 3
- 239000000498 cooling water Substances 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000005253 cladding Methods 0.000 description 2
- 231100000614 poison Toxicity 0.000 description 2
- 125000006850 spacer group Chemical group 0.000 description 2
- 239000000919 ceramic Substances 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 230000007096 poisonous effect Effects 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Inert Electrodes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
〔発明の技術分野〕
本発明は沸騰水型原子炉用の燃料集合体に関す
る。
〔発明の技術的背景〕
沸騰水型原子炉用の燃料集合体の従来例を第１
図から第３図参照して説明する。第１図は燃料集
合体を示す縦断面図で、この燃料集合体１は細長
い円筒状燃料棒４が多数本結束された結束体の上
部が上部タイプレート３により、下部が下部タイ
プレート２によつて接続されている。この結束体
はスペーサ５によつて燃料棒４間が等間隔に保持
されている。前記結束体内には燃料棒４の他に２
本のウオータ・ロツド（図示せず）が組込まれて
いる。この結束体の外周はチヤンネルボツクス６
で包囲され、このチヤンネルボツクス６は上部が
上部タイプレート３に、下部が下部タイプレート
２に接合されている。
燃焼棒４は被覆管７内に図示しない円栓状の
UO2燃料ペレツトが多数装填されたものであり、
この被覆管７の上下両端は上部端栓８及び下部端
栓９で密封されている。上部端栓８は上部タイプ
レート３中の支持空所に挿入することができる延
長部を備えている。下部端栓９は下部タイプレー
ト２中の支持空所に嵌合する嵌合部を備えてい
る。
第２図は上記燃料集合体の横断面図を示すもの
で、燃料棒４が８行８列に正方配列された例であ
る。同図に示される様に燃料棒４はチヤンネルボ
ツクス６の長手方向に垂直な内面で相互に等間隔
を存して８行８列に正方配列されている。また最
外周の燃料棒４とチヤンネルボツクス６との間隙
を水ギヤツプと呼んでいるが、この水ギヤツプも
前記燃料棒４相互の間隔とほぼ等しく設定されて
いる。このような燃料集合体１は４体１組となつ
て炉心内に正方配列されその燃料集合体間の中央
に制御棒１０が挿入されて一つの単位格子を形成
している。この燃料集合体１は出力を平均化する
ために、チヤンネルボツクス６内に２本のウオー
タ・ロツド１１及び８本のガドリニア入り燃料棒
12が組み込まれている。すなわち、２本のウオー
タ・ロツド１１は中心部に対角線状に配列され、
ガドリニア入り燃料棒１２は正方配列された燃料
棒４の最外周から２周目に配置されている。
このガドリニア入り燃料棒１２は燃料ペレツト
に熱中性子を吸収する可燃性毒物としてのガドリ
ニア（Gd2O3）を数％混入したものである。
第３図はウオータ・ロツドの側面図を示すもの
で、同図に示す様に前記ウオータ・ロツド１１は
ジルカロイ製中空管１３の両端に同じくジルカロ
イ製の上部端栓１５と下部端栓１５とを溶接した
構成よりなつている。又、この中空管１３にはス
ペーサ５の間隔を保証するためのタブ１６が合計
14個溶接されている。中空管１３の下端付近には
複数個の冷却水入口孔１７が、上端付近には複数
個の冷却水出口孔１８が設けられており、原子炉
の運転中には中空管１３の内部を冷却水が下方か
ら上方へ流通するように成つている。また、前記
燃料棒４には下表に示すようにU235含有率を５段
階に変化させた５種類の燃料ペレツトが装填され
ている。
TECHNICAL FIELD OF THE INVENTION The present invention relates to a fuel assembly for a boiling water nuclear reactor. [Technical background of the invention] The first conventional example of a fuel assembly for a boiling water reactor is
This will be explained with reference to FIGS. FIG. 1 is a vertical cross-sectional view showing a fuel assembly, in which the upper part of the bundle of elongated cylindrical fuel rods 4 is connected to the upper tie plate 3, and the lower part to the lower tie plate 2. It is connected accordingly. In this bundle, the fuel rods 4 are maintained at equal intervals by spacers 5. In addition to the fuel rods 4, there are 2 fuel rods in the bundle.
A book water rod (not shown) is incorporated. The outer periphery of this bundle is channel box 6.
The channel box 6 is connected to the upper tie plate 3 at the upper part and to the lower tie plate 2 at the lower part. The combustion rod 4 has a plug-like shape (not shown) inside the cladding tube 7.
It is loaded with a large number of UO 2 fuel pellets,
Both upper and lower ends of the cladding tube 7 are sealed with an upper end plug 8 and a lower end plug 9. The upper end plug 8 is provided with an extension that can be inserted into a support cavity in the upper tie plate 3. The lower end plug 9 has a fitting portion that fits into a support cavity in the lower tie plate 2. FIG. 2 shows a cross-sectional view of the fuel assembly, in which the fuel rods 4 are arranged squarely in eight rows and eight columns. As shown in the figure, the fuel rods 4 are squarely arranged in 8 rows and 8 columns at equal intervals on the inner surface perpendicular to the longitudinal direction of the channel box 6. Further, the gap between the outermost fuel rods 4 and the channel box 6 is called a water gap, and this water gap is also set to be approximately equal to the spacing between the fuel rods 4. Four such fuel assemblies 1 are arranged squarely in the reactor core, and a control rod 10 is inserted in the center between the fuel assemblies to form one unit cell. This fuel assembly 1 includes two water rods 11 and eight gadolinia-containing fuel rods in a channel box 6 in order to average the output.
12 are included. That is, the two water rods 11 are arranged diagonally in the center,
The fuel rods 12 containing gadolinia are arranged at the second round from the outermost circumference of the squarely arranged fuel rods 4. This gadolinia-containing fuel rod 12 is made by mixing several percent of gadolinia (Gd 2 O 3 ) as a burnable poison that absorbs thermal neutrons into fuel pellets. FIG. 3 shows a side view of the water rod, and as shown in the same figure, the water rod 11 has an upper end plug 15 and a lower end plug 15 also made of Zircaloy at both ends of a hollow tube 13 made of Zircaloy. It has a welded structure. Additionally, this hollow tube 13 has a total of tabs 16 for ensuring the spacing between the spacers 5.
14 pieces are welded. A plurality of cooling water inlet holes 17 are provided near the lower end of the hollow tube 13, and a plurality of cooling water outlet holes 18 are provided near the upper end. The cooling water is configured to flow from the bottom to the top. Furthermore, the fuel rods 4 are loaded with five types of fuel pellets with U 235 content varying in five levels as shown in the table below.
以上説明したように従来の燃料集合体１は熱中
性子束レベルの高い燃料集合体１の外周部に配置
された燃料棒４のU235含有率が低いために燃料集
合体１の反応度が低く燃料経済性および燃料健全
性が劣る欠点もあつた。
〔発明の目的〕
本発明の目的は、各燃料棒の反応度及び出力を
均一化して燃料経済性及び燃料健全性を向上させ
た燃料集合体を提供することにある。
〔発明の概要〕
本発明は横断面がほぼ正方形のチヤンネルボツ
クス内に複数本の燃料棒をほぼ等間隔に結束して
配列し、かつ中央部分にウオータ・ロツド部を配
列した沸騰水型原子炉用燃料集合体において、前
記ウオータ・ロツド部の横断面積は前記燃料棒の
４本分以上の横断面積を有し、かつ可燃制毒物入
り燃料棒を複数本最外周に配列し、しかも前記燃
料棒それぞれの核分裂性核種の含有率は非均一と
したことを特徴とする燃料集合体にある。
〔発明の実施例〕
第４図および第５図を参照して本発明に係る燃
料集合体の第１実施例を説明する。
第４図は本発明の第１実施例の横断面図を示
し、図中第２図と同一部分には同一符号を付し重
複する部分の説明を省略する。同図において、燃
料集合体２０のチヤンネルボツクス６内にたてよ
こそれぞれ８列に燃料棒２１が正方配列されてい
るが、中央部の４本が抜き出されて、その抜き出
された中央部には４本のウオータ・ロツド１１が
挿入配置されている。また、燃料棒２１の正方配
列中の最外周にはそれぞれコーナーロツド１９を
囲むように対角線上に２本のガドリニア入り燃料
棒１２が配置されており、この燃料棒１２は合計
８本がチヤンネルボツクス６内に配列されている
ことになつている。
以上の構成より本発明は正方配列の中央部に４
本のウオータ・ロツド１１が配置されているの
で、正方配列の中央部における中性子減速効果が
大きくなり燃料集合体２０の中央部の熱中性子束
が増加する。したがつて、ウオータ・ロツド１１
周辺の燃料棒２１の反応度が向上し、特にウオー
タ・ロツド１１に隣接する燃料棒２１では出力が
約10％向上する。よつて、正方配列の中央部に配
置された濃縮度の高い燃料棒２１の出力を向上さ
せることができる。また、ガドリニア入り燃料棒
１２を正方配列の最外周、例えばコーナーロツド
１９を囲む対角線上に配置したので正方配列の外
周部における熱中性子束を減少させることができ
る。したがつて、正方配列の外周部に配置された
燃料棒２１の出力が低下し、外周部に配置された
燃料棒の出力が異常に上昇することが防止され
る。以上により燃料集合体２０の横断面内におけ
る出力を平均化することができる。
第１実施例において、全燃料棒の平均出力に対
する各燃料棒２１の出力の相対値を示す局所ピー
キング係数を算出すると1.1程度となり、従来例
より大幅に平坦化でき燃料健全性が向上する。ま
た従来、熱中性子束レベルが低かつた正方配列の
中央部で出力が増大し、かつ中央部の燃料棒２１
のU235含有率が高いため、燃料集合体２０全体と
して反応度が上昇する。
ここで第５図に燃料集合体について、出力運転
時における核分裂反応系の連鎖反応の起こり易す
さを示す無限増倍率K∞と核燃料の消費割合を示
す燃焼度GWD／Ｔとの関係を示す。図中、実線
は本発明の第１実施例の特性曲線であり、破線は
従来例の特性曲線である。同図において前記燃焼
度10GWD／Ｔ以上では実線のK∞の値が0.5％程
度向上していることが認められる。よつて、本発
明は従来例と比較して核燃料を有効に消費するこ
とができ、燃料経済性を向上させることができ
る。なお、本実施例では、燃料集合体２０内の濃
縮度分布を従来例と同様に構成したが、局所出力
ピーキング係数を従来例と同様にする場合におい
ては、燃料棒２１の核分裂性核種であるU235の含
有率を２〜３種類にすることができる。このため
燃料棒２１の製造及び燃料集合体の組立て作業及
びその管理を容易にすることができる。
次に第６図に参照して本発明の第２実施例を説
明する。ここで第６図に本発明の第２の実施例の
横断面図を示す。なお、図中第１実施例と同様の
ものには同一符号を付し重複する部分の説明を省
略する。同図において、燃料集合体２２の中央部
には従来より内径が大きくかつ単一の円筒形ウオ
ータ・ロツド２３が挿入されている。このウオー
タ・ロツド２３の内径は従来のウオータ・ロツド
１１の４本分に相当する横断面積を有する内径に
選定されている。
この第２実施例では前記第１実施例で得られる
作用効果に加えて、ウオータ・ロツド２３が単一
のものであるため、さらに燃料集合体２２の組立
て作業を容易にすることができる。なお、第２実
施例ではウオータ・ロツド２３は円筒で示したが
角形断面を有するものでもよい。
第７図は本発明の第３実施例を示したものであ
る。同図に示すように第３実施例はウオータ・ロ
ツド１１の本数を第４図の４本から12本に増加さ
せた例である。この第３実施例では前記第１実施
例で得られる作用効果に加えてウオータ・ロツド
１１の本数を増加させているため、正方配列の中
央部における中性子減速効果がさらに大きくなり
燃料集合体２５の中央部の熱中性子束が増加す
る。したがつて、ウオータ・ロツド１１周辺の燃
料棒２１の反応度が向上し、第１実施例よりさら
に燃焼効率を向上させることができる。
次に第８図を参照して本発明の第４実施例を説
明する。ここで第８図は第４実施例の燃料集合体
を示す横断面図である。同図において、ガドリニ
ア入り燃料棒１２の配置は第１実施例からずらし
て配置されている。この構成より燃焼集合体２６
の熱中性子束の分布が変化してもその変化に応じ
て第１実施例と使い分け燃料棒２１の燃焼度を調
整することができる。
第９図は第５実施例の燃料集合体を示す横断面
図である。第５実施例の燃料集合体２７は第２図
に示した最も熱中性子束レベルが高いコーナーロ
ツド１９の代りに軸方向に中空部を形成した円筒
形UO2ペレツト又は細径のペレツトもしくはUO2
粉末にZrO2等の中性子を殆んど吸収しないセラ
ミツク混合して増量した低密度ペレツト等を装填
した燃料棒２４に置き換えかつ第６図に示したよ
うに単一のウオータロツド２３を挿着した構成で
ある。この構成によつて、燃料棒２４付近のU235
の含有率を低く抑さえ、さらに燃料集合体２７の
出力分布を均一化させることができる効果があ
る。
〔発明の効果〕
本発明によれば、各燃料棒の出力分布を均一化
して燃料棒の健全性を向上させるとともに、核燃
料を有効に消費し燃料経済性を向上させることが
できる。
As explained above, in the conventional fuel assembly 1, the reactivity of the fuel assembly 1 is low because the U 235 content of the fuel rods 4 arranged at the outer periphery of the fuel assembly 1, where the thermal neutron flux level is high, is low. It also had the disadvantage of poor fuel economy and fuel integrity. [Object of the Invention] An object of the present invention is to provide a fuel assembly in which the reactivity and output of each fuel rod are equalized to improve fuel economy and fuel soundness. [Summary of the Invention] The present invention provides a boiling water nuclear reactor in which a plurality of fuel rods are bundled and arranged at approximately equal intervals in a channel box having an approximately square cross section, and a water rod is arranged in the center. In the fuel assembly for the fuel assembly, the cross-sectional area of the water rod portion has a cross-sectional area equal to or more than four of the fuel rods, and a plurality of fuel rods containing a burnable poisonous substance are arranged on the outermost periphery, and The fuel assembly is characterized in that the content of each fissile nuclide is non-uniform. [Embodiment of the Invention] A first embodiment of the fuel assembly according to the present invention will be described with reference to FIGS. 4 and 5. FIG. 4 shows a cross-sectional view of the first embodiment of the present invention, in which the same parts as those in FIG. In the same figure, fuel rods 21 are squarely arranged in eight rows in both the vertical and horizontal directions in the channel box 6 of the fuel assembly 20, and the four rods in the center are extracted. Four water rods 11 are inserted in the holder. Furthermore, two gadolinia-containing fuel rods 12 are arranged diagonally on the outermost periphery of the square array of fuel rods 21 so as to surround the corner rods 19, and a total of eight fuel rods 12 are placed in the channel box 6. It is supposed to be arranged within. With the above configuration, the present invention has four
Since the water rods 11 are arranged, the neutron moderation effect at the center of the square arrangement becomes large, and the thermal neutron flux at the center of the fuel assembly 20 increases. Therefore, water rod 11
The reactivity of the surrounding fuel rods 21 is improved, and in particular the output of the fuel rods 21 adjacent to the water rod 11 is increased by about 10%. Therefore, the output of the highly enriched fuel rods 21 arranged in the center of the square arrangement can be improved. Further, since the gadolinia-containing fuel rods 12 are arranged at the outermost periphery of the square arrangement, for example on the diagonal line surrounding the corner rods 19, the thermal neutron flux at the outer periphery of the square arrangement can be reduced. Therefore, the output of the fuel rods 21 arranged on the outer periphery of the square array is reduced, and the output of the fuel rods arranged on the outer periphery is prevented from increasing abnormally. As described above, the output within the cross section of the fuel assembly 20 can be averaged. In the first embodiment, the local peaking coefficient indicating the relative value of the output of each fuel rod 21 with respect to the average output of all fuel rods is calculated to be about 1.1, which is much flatter than the conventional example and improves fuel integrity. In addition, conventionally, the output increased in the center of the square array where the thermal neutron flux level was low, and the fuel rods 21 in the center
Since the U 235 content is high, the reactivity of the fuel assembly 20 as a whole increases. Here, FIG. 5 shows the relationship between the infinite multiplication factor K ∞ , which indicates the likelihood of a chain reaction occurring in the nuclear fission reaction system, and the burnup GWD/T, which indicates the consumption rate of nuclear fuel, for a fuel assembly during power operation. In the figure, the solid line is the characteristic curve of the first embodiment of the present invention, and the broken line is the characteristic curve of the conventional example. In the same figure, it is recognized that the value of K ∞ shown by the solid line improves by about 0.5% at burnup of 10 GWD/T or more. Therefore, the present invention can consume nuclear fuel more effectively than the conventional example, and can improve fuel economy. In this example, the enrichment distribution within the fuel assembly 20 is configured in the same manner as in the conventional example, but when the local power peaking coefficient is made the same as in the conventional example, the fissile nuclide of the fuel rod 21 The content of U 235 can be adjusted to 2 to 3 types. Therefore, manufacturing of the fuel rods 21, assembly of the fuel assembly, and management thereof can be facilitated. Next, a second embodiment of the present invention will be described with reference to FIG. FIG. 6 shows a cross-sectional view of a second embodiment of the present invention. Components in the drawings that are similar to those in the first embodiment are denoted by the same reference numerals, and explanations of overlapping parts will be omitted. In the figure, a single cylindrical water rod 23, which has a larger inner diameter than the conventional one, is inserted into the center of the fuel assembly 22. The inner diameter of this water rod 23 is selected to have a cross-sectional area equivalent to four conventional water rods 11. In this second embodiment, in addition to the effects obtained in the first embodiment, since the water rod 23 is a single one, the assembly work of the fuel assembly 22 can be further facilitated. In the second embodiment, the water rod 23 is shown as a cylinder, but it may have a rectangular cross section. FIG. 7 shows a third embodiment of the present invention. As shown in the figure, the third embodiment is an example in which the number of water rods 11 is increased from four in FIG. 4 to twelve. In this third embodiment, in addition to the effects obtained in the first embodiment, the number of water rods 11 is increased, so that the neutron moderation effect in the center of the square arrangement is further increased, and the fuel assembly 25 is Thermal neutron flux in the center increases. Therefore, the reactivity of the fuel rods 21 around the water rods 11 is improved, and the combustion efficiency can be further improved than in the first embodiment. Next, a fourth embodiment of the present invention will be described with reference to FIG. Here, FIG. 8 is a cross-sectional view showing the fuel assembly of the fourth embodiment. In the figure, the arrangement of the fuel rods 12 containing gadolinia is shifted from that of the first embodiment. With this configuration, the combustion assembly 26
Even if the distribution of thermal neutron flux changes, the burnup of the fuel rod 21 can be adjusted according to the change depending on the first embodiment. FIG. 9 is a cross-sectional view showing the fuel assembly of the fifth embodiment. The fuel assembly 27 of the fifth embodiment is a cylindrical UO 2 pellet or a small diameter pellet or a UO 2 pellet with a hollow part formed in the axial direction instead of the corner rod 19 shown in FIG. 2 , which has the highest thermal neutron flux level.
A configuration in which the fuel rod 24 is replaced with a fuel rod 24 loaded with low-density pellets, etc., which are increased by mixing the powder with ceramics such as ZrO 2 that hardly absorb neutrons, and a single water rod 23 is inserted as shown in FIG. It is. With this configuration, U 235 near the fuel rod 24
This has the effect of keeping the content low and further making the power distribution of the fuel assembly 27 uniform. [Effects of the Invention] According to the present invention, the power distribution of each fuel rod can be made uniform to improve the soundness of the fuel rods, and nuclear fuel can be consumed effectively to improve fuel economy.
第１図は従来の燃料集合体を示す縦断面図、第
２図は第１図における燃料集合体の横断面図、第
３図は第１図におけるウオータ・ロツドの斜視
図、第４図は本発明の第１の実施例を示す燃料集
合体の横断面図、第５図は従来例と本発明例にお
ける無限増倍率と燃焼度の特性を比較して示す特
性図、第６図ないし第９図はそれぞれ本発明の第
２の実施例ないし第５の実施例を示す燃料集合体
の横断面図である。
１１……ウオータ・ロツド、１２……ガドリニ
ア入り燃料棒、２０……燃料集合体、２１……燃
料棒、２２……燃料集合体、２３……ウオータ・
ロツド、２４……燃料棒、２５……燃料集合体、
２６……燃料集合体、２７……燃料集合体。
Fig. 1 is a longitudinal sectional view showing a conventional fuel assembly, Fig. 2 is a cross sectional view of the fuel assembly in Fig. 1, Fig. 3 is a perspective view of the water rod in Fig. 1, and Fig. 4 is a longitudinal sectional view of a conventional fuel assembly. FIG. 5 is a cross-sectional view of a fuel assembly showing the first embodiment of the present invention; FIG. 9 are cross-sectional views of fuel assemblies showing second to fifth embodiments of the present invention, respectively. 11... Water rod, 12... Fuel rod containing gadolinia, 20... Fuel assembly, 21... Fuel rod, 22... Fuel assembly, 23... Water rod.
rod, 24... fuel rod, 25... fuel assembly,
26... fuel assembly, 27... fuel assembly.
Claims (1)
に複数本の燃料棒をほぼ等間隔に結束して配列
し、かつ中央部分にウオータ・ロツド部を配列し
た沸騰水型原子炉用燃料集合体において、前記ウ
オータ・ロツド部の横断面積は前記燃料棒の４本
分以上の横断面積を有し、かつ可燃制毒物入り燃
料棒を複数本最外周に配列し、しかも前記燃料棒
それぞれの核分裂性核種の含有率は非均一とした
ことを特徴とする燃料集合体。 ２ ウオータ・ロツド部は単一のウオータ・ロツ
ドの横断面積が前記燃料棒と同様なウオータロツ
ドを４本以上配列して成ることを特徴とする特許
請求の範囲第１項記載の燃料集合体。 ３ ウオータ・ロツド部は横断面積が前記燃料棒
の４本以上の横断面積を有する単一のウオータロ
ツドより成ることを特徴とする特許請求の範囲第
１項記載の燃料集合体。[Scope of Claims] 1. A boiling water reactor in which a plurality of fuel rods are bundled and arranged at approximately equal intervals in a channel box with a substantially square cross section, and a water rod is arranged in the center. In the fuel assembly, the cross-sectional area of the water rod portion is equal to or more than four of the fuel rods, and a plurality of fuel rods containing a burnable anti-toxic substance are arranged on the outermost periphery, and each of the fuel rods A fuel assembly characterized in that the content of fissile nuclides is non-uniform. 2. The fuel assembly according to claim 1, wherein the water rod portion is formed by arranging four or more water rods having a cross-sectional area similar to that of the fuel rod. 3. The fuel assembly according to claim 1, wherein the water rod portion comprises a single water rod having a cross-sectional area of four or more of the fuel rods.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58234186A JPS60127489A (en) | 1983-12-14 | 1983-12-14 | Fuel aggregate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58234186A JPS60127489A (en) | 1983-12-14 | 1983-12-14 | Fuel aggregate |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60127489A JPS60127489A (en) | 1985-07-08 |
| JPH0552475B2 true JPH0552475B2 (en) | 1993-08-05 |
Family
ID=16967021
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58234186A Granted JPS60127489A (en) | 1983-12-14 | 1983-12-14 | Fuel aggregate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60127489A (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0816711B2 (en) * | 1986-01-31 | 1996-02-21 | 株式会社東芝 | Fuel assembly |
| JPH0713663B2 (en) * | 1986-03-19 | 1995-02-15 | 株式会社日立製作所 | Fuel assembly |
| JPS63241491A (en) * | 1987-03-30 | 1988-10-06 | 原子燃料工業株式会社 | Fuel aggregate for boiling water type reactor |
| GB2378734A (en) | 2001-08-14 | 2003-02-19 | Carmeli Adahan | Disposable pump with detachable motor |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57161581A (en) * | 1981-03-31 | 1982-10-05 | Genshi Nenryo Kogyo | Fuel assembly for bwr type reactor |
| JPS5913981A (en) * | 1982-07-14 | 1984-01-24 | 株式会社東芝 | Fuel assembly |
-
1983
- 1983-12-14 JP JP58234186A patent/JPS60127489A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57161581A (en) * | 1981-03-31 | 1982-10-05 | Genshi Nenryo Kogyo | Fuel assembly for bwr type reactor |
| JPS5913981A (en) * | 1982-07-14 | 1984-01-24 | 株式会社東芝 | Fuel assembly |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60127489A (en) | 1985-07-08 |
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